| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 7.605 (b) | 8.508 (b) | 1.119 | − | 3.496 (b) | 4.943 (b) |
| 2 | (n,elastic) | 6.995 (b) | 7.897 (b) | 1.129 | − | 1.740 (b) | 3.803 (b) |
| 4 | (n,inelastic) | ( E-thr = 674.6 keV ) | 591.2 (mb) | 1.134 (b) | |||
| 16 | (n,2n) | ( E-thr = 10.04 MeV ) | 1.149 (b) | 574.0 (μb) | |||
| 17 | (n,3n) | ( E-thr = 17.09 MeV ) | − | 55.09 (nb) | |||
| 22 | (n,na) | ( E-thr = 7.060 MeV ) | 3.710 (μb) | 11.06 (nb) | |||
| 28 | (n,np) | ( E-thr = 11.56 MeV ) | 5.931 (μb) | 41.31 (nb) | |||
| 102 | (n,γ) | 610.2 (mb) | 610.5 (mb) | 1.000 | 959.5 (mb) | 766.0 (μb) | 5.573 (mb) |
| 103 | (n,p) | ( E-thr = 4.879 MeV ) | 12.45 (mb) | 5.479 (μb) | |||
| 104 | (n,d) | ( E-thr = 9.304 MeV ) | 694.7 (μb) | 189.0 (nb) | |||
| 105 | (n,t) | ( E-thr = 11.97 MeV ) | 16.48e-12 (b) | 1.307 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 12.92 MeV ) | 0.000 (b) | 70.19e-18 (b) | |||
| 107 | (n,a) | ( E-thr = 910.9 keV ) | 1.354 (mb) | 734.5 (nb) | |||
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These cross sections are calculated from JENDL-4.0 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
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